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John, T.M.; Mohanakrishnan, P.; Narayanan, R.
Research co-ordination meeting on updated codes and methods to reduce the calculational uncertainties of liquid metal fast reactor reactivity effects. Working material2000
Research co-ordination meeting on updated codes and methods to reduce the calculational uncertainties of liquid metal fast reactor reactivity effects. Working material2000
AbstractAbstract
[en] The present work is the result of IGCAR, India, for the phase 1 calculations of the BN-600 core benchmark problem. The methods applied consisted of: nuclear data library CV2M; 25 group ABBN type data library for self shielding factors; delayed neutron yield, yield fraction and decay constants, effective cross sections calculated by EFFCROSS code; basic core calculations (RZ model, 25 groups), perturbation calculations (diffusion, first order perturbation). Summary of the results for BN-600 reactor core benchmark (phase 1) include multiplication factors, Doppler coefficients, density coefficients, expansion coefficients, power distribution, beta-eff values, reaction rate distributions
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International Atomic Energy Agency, International Working Group on Fast Reactors, Vienna (Austria); 375 p; 2000; p. 222-248; IAEA-IWGFR research co-ordination meeting on updated codes and methods to reduce the calculational uncertainties of liquid metal fast reactor reactivity effects; Vienna (Austria); 20-24 Nov 2000; Tabs
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Report
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Conference
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BREEDER REACTORS, CROSS SECTIONS, DIFFERENTIAL EQUATIONS, EPITHERMAL REACTORS, EQUATIONS, FAST REACTORS, FBR TYPE REACTORS, LIQUID METAL COOLED REACTORS, LMFBR TYPE REACTORS, NEUTRON TRANSPORT THEORY, POWER REACTORS, REACTIVITY COEFFICIENTS, REACTOR COMPONENTS, REACTORS, SODIUM COOLED REACTORS, TRANSPORT THEORY
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